Specifics on the amount of CPR present in waste containers are not provided in the AK record. As
a conservative measure, it may be assumed that the Type I combustible and Type II filter paper wastes are
predominately CPR, and that some of the Type III filter waste was generated prior to 1957 and is
combustible. it should also be assumed that one-half of the waste identified for the combination of Type I
and V is also comprised of CPR [RF-D001].

There are no written reports of munitions or firearms identified as being placed in waste containers;
however, there is testimony by RFP personnel that there were as many as four revolvers confiscated from

guards by Health Physics on the day of the Building 776 1969 fire [RF-P047]. It is not known whether
munitions were included with the weapons.

4.12.2 Chemical Constituents

A variety of chemicals used during operations conducted in Building 776/777, and the associated

process and/or use are presented in Table 4-36.

Table 4-36. Chemical contaminants used in Building 776/777.

~ “___ Constituent Generator/Procéss/Use (if known)
Organic Compounds
1,1,1-trichloroethane Components cleaning [RF-P084]
Acetone Components cleaning [RF-C167, RF-P084]
Carbon tetrachloride 1957-1969 cleaning and degreasing machined parts
[RF-C234, RF-P047, RF-P084, RF-U143]
Ethanol Components cleaning [RF-P084]
Formula 409 Decontamination and fire clean-up [RF-U167]
Freon Cleaning agent [RF-C502]
Isopropyl alcohol Cleaning activities until 1963-1964 [RF-P084]
Paint; strippable Fire cleanup contamination removal [RF-C171]
Shell Vitrea cutting oil _ , Machining in Building 776 [RF-P084]
Tetrachloroethylene Cleaning and degreasing [RF-C195, RF-P084]
Texaco Regal Oil Machining [RF-P084]
Trichloroethylene 1957-1969 cleaning plutonium parts in assembly process
[RF-C196, RF-P084]
Metals
Beryllium (trace amounts) Metal component [RF-P084, RF-U038, RF-U124,

Chromium (includes chromium
trioxide)

Gallium

Lead

RF-U150]

Anti-microbial additive to Kathene air drying system
[RF-P084] .

Alloying plutonium [RF-C502]

Shielding in the form of lead and leaded glass; leaded
rubber gloves; welding rods [RF-P047, RF-P084,
RF-U124, RF-U167]

4-68


Table D-34, Lowry Air Force Base waste types by year of shipment.
Lowry Alr Force Base (LAFB) Waste Types
Volume (cubic feat)

Year of
Shipment

Combustible
Debris (I)

Combustible/|
Non-
Combustible
Debris (1,V)

Filter Paper
a)

Filters (iil)

| Sludge Waste|
(M)

Non-
Combustible
Debris (V)

OivOrganic
‘Sludge (Vi)

Contaminated]

Berylitum
Debris (Vil)

1954
1955,
1956
1957
1958
1959
1960
1961
1962
1963
1964
1965
1966
1967
| 1968 —|
1969
1970

FeABSYoodo

ecco oeCeSd

|

eooeecece

exeoox000

|

eo0c0cece

|

TOTAL (ft")

a

eloeacnec coc ec OoGC CCC)

OO Ce ee ee)

elococeceacceecaccoccsd

ey

Cr ee ee)

lelos GODS OCC COO OC COC SD

Acchart was not created for this bullding due to the small volume of waste and/or few waste types

Table D-35. Lawrence Radiation Lab waste types by year of shipment.

Lawrence Radiation Lab (LRL) Waste Types
Volume (cubic feet)

Year of
‘Shipment

Combustible
Debris (1)

Combustible/|
Non-
Combustible
Debris (LV)

Filter Paper
aw

Filters (Il!)

Sludge Waste]
Mw

Non-
Combustible
Debris (Vv)

Oiv/Organic
‘Sludge (Vi)

Beryllium
Contaminated}
Debris (Vil)

1954
1955
1956
1957
1958
1959
1960
1961
1962
1963
1964
1965
1966
1967
1968
1989
1970

TOTAL (ff)

8
Bloc coccoZoccccccce

elococeecccc coco cCCod

elooac De DCD DD CO COC ORD

Ce ee)

jelomoecaccc ecco eeo

SO ee ee

eloccoeccoccoc occ cccesd

S Ce ee ee ee ee

A chart was not created for this buliding due to the small volume of waste and/or few waste types

D4l


Sra

200000

150000

400000

Volume (cubic feet)

-50000 +#

Total RFP Wastes (Including Dow) !

Year of Shipment

+= Combustible Debris (1)
Filters (It)
—- olV/organic Sludge (V1)

U233 Contaminated Debris (I,V)

—#— Combustible/Non-Combustible Debris (1,V)
—*-Sludge Waste (IV)
— Beryllium Contaminated Debris (VII)

Filter Paper (It)
—®—Non-Combustible Debris (V)
—— 233 Contaminated Sludge (IV)

Figure D-16, Total RFP waste by year of shipment. \



Table 4-24. (continued).

"Constituent

Generator/Process/Use (if known)

Silver solder (contained cadmium)

Other Chemicals/Constituents

Aluminum nitrate
Amercoat paint
Ammonium hydroxide
Ammonium sulfate
Ammonium thiosulfate
Ascorbic acid

Calcium chloride
Calcium fluoride
Chromic acid
Dowex 1 and 21K.
Dowex 50
Ferrous sulfamate

Ferrous sulfate
Fluorine

Fluorinert liquids (FC-40, FC-43,
FC-75, FC-77, FC-78, FC-88)

Fluosilicic acid

Glycerol

Gulf BT

Hollingshead 333 Cocoon
Hydrazine

Hydrochloric acid

Hydrofluoric acid
Hydrogen fluoride; anhydrous

Hydrogen peroxide (35 and 50%)
Hydroiodic acid

Hydroxylamine hydrochloride

Maintenance [RF-P040, RF-C499]

Anion exchange [RF-P084, RF-P091, RF-P260]
Floor and equipment paint [RF-P262]

78 recovery [RF-P263]

Peroxide precipitation [RF-P264]

Peroxide precipitation [RF-P260]

Neptunium precipitation, americium purification
[RF-C502, RF-P260]

Direct oxide reduction [RF-P 108}
Dissolution [RF-P084, RF-P091]

~ “Plutonium metallurgical R&D [RF-U202]

Anion exchange resin [RF-C502]
Cation exchange resin [RF-C502]

Anion exchange, neptunium anion exchange[RF-P084,
RF-P091, RF-P260]

Neptunium anion exchange [RF-P260]
Anion exchange, neptunium anion exchange [RF-C502]
Product R&D [RF-P272]

Formed in anion exchange [RF-P264]

Plutonium metallurgical R&D [RF-U201]

Solvent extraction [RF-P264]

Paint stripping, contamination fixative [RF-U139]
Neptunium anion exchange [RF-P260]

Americium cation exchange, neptunium precipitation,
laboratory [RF-P091, RF-P260]

Dissolution [RF-P091, RF-P260]

Hydrofluorination, fluid-bed fluoridation [RF-P084,
RF-PO91] .

Peroxide precipitation [RF-P084]

Neptunium anion exchange, neptunium precipitation
[RF-P260]
Neptunium precipitation [RF-P260] ,

4-47


The volume of the waste types (I through VII) and noncombustible debris from ”*U process and
empty drums generated from Building 881 is presented by year of shipment in Appendix D (Table D-21
and Figure D-11). The increases in combustible and noncombustible debris wastes during the late 1960s
as EU operations in Building 881 wound down as illustrated in Figure D-11. During clean out, an increase
in debris would have been expected.

4.14.2. Chemical Constituents

A variety of chemicals was used in Building 881 waste generating processes. The chemicals and
the corresponding process or use, if known, are presented in Table 4-42.

Table 4-42. Chemicals used in Building 881.

Constituent Generator/Process/Use (if known)

Organic Compounds

1,1,1-trichloroethane Laboratory use [RF-C214]

Acetic acid Unknown—chemical inventory [RF-C227]

Aleoliol’ == hemical inventory [RF-C227]~

Anchorlube Unknown—chemical inventory [RF-C215]

Carbon tetrachloride Laboratory use [RF-C214]

Chloroform Laboratory use [RF-C214]

Citric acid EU recovery [RF-P084]

Dibutylcarbitol EU recovery [RF-P084]

Epoxy glues Special projects [RF-P084]

Ethanol Special projects [RF-P084]

Ethylene dibromide Laboratory use [RF-C214]

Ethylene dichloride Laboratory use [RF-C214]

Freon; unspecified EU recovery [RF-P084]

Freon 113 Special projects [RF-P084]

Freon 12 Special projects [RF-P084]

Genesolv-D (trichlorotrifluoroethane} | Unknown—chemical inventory [RF-C215]

Lubricating oil : Special projects [RF-P084]

Malonic acid EU recovery [RF-P084]

Methylene chloride Laboratory use [RF-C214]

Nitradd EU recovery [RF-P084]

Ortho-dichlorobenzene Laboratory use [RF-C214]

Oxalic acid Unknown—chemical inventory [RF-C227]

Sani-Phene Disinfectant Unknown—chemical inventory [RF-C215]

Tetrachloroethylene EU recovery [RF-P084]

Texaco Soluble D Unknown—chemical inventory [RF-C215]

Transul Tex 210 Unknown—chemical inventory [RF-C215]

Trichloroethylene Laboratory use [RF-C214, RF-C227]

4-79


Table D-36. Martin Aircraft waste types by year of shipment,
Martin Aircraft (Mariin) Waste Types
Volume (cubic feet)

Year of
‘Shipment

Combustible
Debris (I)

Combustible!
Non-
Combustible
Dabris (IV)

Filter Paper

Fitters (Itt)

Sludge Waste!
ayy

Non-
Combustible
Debris (¥)

OWOrgantc
‘Sludge (Vi)

Beryllium
Contaminated!
Debris (Vil)

1954,
1955
1956
1957
1958
1959
1960
1961
1962
1963,
1964
1965,
1966
1967
1868" |
1969
1970

eoeaccp cece aeDe

0
oO

|

ecoaceceooocd

TOTAL (ty

elooceovcecascececcnd

Blo op o DD CH COD OOROoO

eloocccceon ecco ooo Co

A chart was not created for this building due to the small volume of waste and/or few waste types

Table D-37. Colorado School of Mines waste types by year of shipment,
Colorado Schoo! of Minas (SOM) Waste Types
Volume {cubic foe!)

Year of
Shipment

Combustible
Debris (1)

Combustible!
Non-
Combustible
Debris (,V)

Filter Paper
0)

Fitters (Il)

Sludge Waste]
TM

Non-
Combustible
Debris (V)

oWwOrganic
Sludge (V1)

Berylllum
Contaminated]
Debris (vil)

1954
1955,
1956
1957
1958
1959
1960
1964
1962
1963
1984
1965
1966
1967
1968
1969
1970

gloooceo¥Noacccccocd

elooooc acco ese eo oood

elooosc ce aan oe ceoed

ejooooacccaseecoCeS

apjoccoeo eon oD DO GeODd

Joo Co CONDO eOCoCCeODS

ejoocoacco cee ce Co GO SD

elooaonccece oc oc eood

TOTAL (ft}

A chart was not created for this bulkjing due to the small volume of waste and/or few waste types.

D-42


identified in the late 1950s [RF-C124]. It is assumed that this sludge was from an accumulation of liquid
waste material within processing equipment [RF-U115, RF-U1070].

4.5.2 Chemical Constituents

Chemicals and other potential waste constituents used in Building 444 are listed in Table 4-13.
Cleaning solvents and other chlorinated compounds used in Building 444 operations included
trichloroethylene (TCE), tetrachloroethylene (PCE), and chlorofluoro-hydrocarbons (CFCs) such as
Freon, chloroform, tetrabromoethylene, and 1,1,1-trichloroethane (TCA). Spent solvents and other liquid
wastes were sent to Building 774 for recycle and reuse or treatment and disposal. The spent salt baths
contaminated with uranium oxide were identified as Type IV sludge waste either for this building.

Metals were identified as used in Building 444 processes such as metal etching and plating
operations, or treatment of uranium parts prior to coating. The metals identified as potentially present in
Building 444 waste are listed in Table 4-13 [RF-P085].

Table 4-13. Chemicals used in Building 444.

Constituent Generator/Process/Use (if known)
* Organic Compounds

1,1,1-trichloroethane Replaced perchloroethylene for cleaning, machining,
chemistry technology [RF-P084, RF-U115]

Acetone Parts cleaning [RF-P085]

Carbon (graphite) Unknown [RF-C502]

Celvacene Grease Miscellaneous materials [RF-C215]

Chlorofluorocarbons Cleaning solvent [RF-U115]

Chloroform Chemistry technology [RF-P085]

Dimethylsulfoxide solution Unknown [RF-C502]

Ethanol Chemical inventory [RF-C215]

Freons; Parts cleaning—physical metallurgy [RF-P040, RF-P084]

Freon TF-113 and Freon TF Photo-processing chemical [RF-C215]

Kerosene Unknown—chemical inventory [RF-C215]

Methanol Joinings and coatings [RF-P040]

Motor oil 20-W Unknown

Tetrabromoethylene Float sink separation process media in conjunction with
beryllium work [RF-P084]

Tetrachloroethylene Used to clean coolants off of machined parts [RF-P084}
Used to remove the dye penetrant from parts [RF-C215]

Trichloroethylene Cleaning solvent and degreasing [RF-U115]

Trichloromethane <2: ..=u::. Parts cleaning prior to product inspection [RF-P084].._.

Metals
Aluminum Physical metallurgy [RF-P085]

4-17


(This page intentionally left blank).

D-46


Table 4-36. (continued).

Constituent Generator/Process/Use (if known)
Lithium Special order work [RF-P064]
Magnesium Carrier on the conveyor lines [RF-C502]
Silver Metal component [RF-P084]
Other Chemicais/Constituents
Calcium fluoride Mold coating [RF-C502]
Lithium chloride (Kathene) Solution used for air-drying system [RF-P084]
Magnesium chloride MSE
Nitric acid [RF-U143]
Potassium chloride MSE
Sodium chloride MSE

442.3 Radionuclides

Weapons grade plutonium, EU, and DU were commonly used in the Building 776/777 processes.
‘These radioisotopes and related isotopes that may be present in wastes generated from Building 776/777
are listed in Table 4-37. Radioisotopic content for individual wastes or specific to the RFP buildings
cannot be determined; however, radioisotopic content for all RFP waste was estimated and is discussed in
detail in Section 7.

Table 4-37. Radioisotopes expected to be present in Building 776/777 wastes [RF-P084, RF-P085,
RF-U15]. :

Radionuclides
241 ‘Am 23ND
28py Alpy
5p y iy
240py ioe
22py 2387



EU
EWR

Icc
IDC
IDR
in.
INEEL
kg

LAFB
Ib
LGW
LLW
LRL

“Glovebox Excavator Method” ~

enriched uranium
Early Waste Retrieval
foot

square foot

gram

gram per cubic foot
gram per gram

gram per liter

gallon

high-efficiency particulate air (filter)
hour

hazardous waste number

Immediate Action Directive
Interstate Commerce Commission
item description code

initial drum retrieval

inch(s)

Idaho National Engineering and Environmental Laboratory
kilogram

liter

Lowry Air Force Base

pound

line-generated waste

low-level waste

Lawrence Radiation Laboratory

viii


Table 4-39. (continued).

Constituent Generator/Process/Use (if known)
Magnesium chloride Pyrochemical operations [RF-C502]
Nickel (nickel sulfate crystals) Chemistry technology [RF-P085]
Nitric acid Chemistry technology, physical metallurgy, joining and
coatings [RF-P040, RF-P085]
Oakite Unknown [RF-U188]
Perchloric acid Chemistry technology [RF-U208]
Phosphoric acid Joining and coatings [RF-P040]
Potassium chloride Pyrochemical operations [RF-C502]
Potassium chromate Unknown [RF-P085]
Potassium dichromate Physical metallurgy [RF-P085]
Soda lime Chemistry technology [RF-P040]
Sodium chloride—~~ ~ ~~ ~ Pyrochemical Operations [RF-C502] a
Sodium dichromate Chemistry technology [RF-P085]
Sodium hydroxide Joining and coatings [RF-P040]
Sulfuric acid Joining and coatings [RF-P040]
Xenon trioxide Chemistry technology [RF-U208]

a, Common laboratory solvents.

4.13.3 Radionuclides

Actinide elements, compounds, and other radioactive materials encountered in the process
chemistry laboratories included the isotopes listed in Table 4-40 as well as other associated tracer isotopes
or radioactive decay products. Radioisotopic content for individual wastes or specific to RFP buildings
cannot be determined. Radioisotopic content for all RFP waste is discussed in detail in Section 7.

Table 4-40. Radioisotopes expected to be present in Building 779 wastes [RF-P040, RF-P084, RF-P085,
RF-U115].

Radionuclides : Additional Radionuclides

2 Amn C9
=Pa *H

By BNp

240py 24Ipy

2p y . 22TH
28 2347

Sr CY) =5y

4-73


Dat.


Building 883 was filled with oil containing PCBs, but it is not known whether oil from this machine was .
ever treated in Building 774 [RF-C058, RF-C426, RF-P047, RF-P084, RF-P090, RF-U115].

Table 4-33. Chemicals used in Building 774.

Constituent Generator/RF-Process/Use (if known)
Organic Compounds
Carbon; activated First and second stage processing [RF-C096, RF-C132,
RF-P098, RF-P108, RF-P165, RF-U111, RF-U283]
Separan® First and second stage processing [RF-C096, RF-C132,
RF-P098, RF-P108, RF-P165, RF-U110]
Separan.2610® First and second stage processing [RF-U111, RF-U283]
Other Chemicals/Constituents

Ferric hydroxide or aluminum
hydroxide

" Ferric sulfate

Ferric sulfate and calcium chloride or
magnesium sulfate

Ferrous chloride and calcium
hydroxide

Ferrous sulfate

Ferrous sulfate (aluminum hydroxide
may be used)

HTH. and Norite A
Lime and caustic soda

Lime and sodium hydroxide

Lime and sodium hydroxide, calcium
hydroxide, or potassium hydroxide

Lime and sodium hydroxide or
potassium hydroxide

Purifloc 501®

Super RF-Cell

First and second stage processing [RF-U111]

First and second stage processing [RF-C096, RF-P098,
RF-P108, RF-P165]

First and second stage processing [RF-P047, RF-P260,
RF-P265, RF-U115, RF-C522]

First and second stage processing [RF-C132, RF-U110]

First and second stage processing [RF-U048]
First and second stage processing [RF-U111, RF-U283]

First and second stage processing [RF-U048]

First and second stage processing [RF-C132, RF-U110,
RF-U111, RF-U283]

First and second stage processing [RF-U048]

First and second stage processing [RF~C096, RF-P098,
RF-P108, RF-P165]

First and second stage processing [RF-P047, RF-P260,
RF-P265, RF-U115, RF-C522]

First and second stage processing [RF-P047, RF-P260,
RF-P265, RF-U115, RF-C522]

Used as filter aid in first and second stage processing
[RF-Ui11, RF-U283]

4-61


4.9.2 Chemical Constituents

Chemicals used in plutonium manufacturing processes conducted in Building 707 may be present
as waste contaminants generated in Building 707 and are listed in Table 4-21.

Table 4-21. Chemicals used in Building 707.

Constituent Generator/Process/Use (if known)
Organic Compounds

Acetone Cleaning prior to brazing [RF-P084]

Carbon tetrachloride Cleaning and degreasing [RF-P084]

Ethanol Components cleaning [RF-P084]

Freon (compound unspecified) Leak testing of tantalum crucibles [RF-U084]

Freon 113 Density testing of plutonium parts, cooling, and
lubrication during beryllium machining and destructive
testing [RF-P084] © -

Isopropyl alcohol Cleaning of compressors [RF-P084]

Oil, unnamed light Equipment lubrication during beryllium machining
[RF-P084]

Texaco 634 oil Machining [RF-P084]

Texaco Regal Oil Machining [RF-U115]

Trichloroethane Cleaning of plutonium parts [RF-P084]

Trichloroethylene Cleaning plutonium parts in assembly process [RF-P084]

Metals

Beryllium (trace amounts) Metal component [RF-P084, RF-U115]

Lead Shielding in the form of lead and leaded glass; leaded
rubber gloves; welding rods [RF-P047, RF-P084]

Other Chemicals/Constituents

Calcium fluoride Coating graphite molds [RF-P084]

Developer Inspection/testing of welds [RF-P084]

Electro etch Mark imperfections on plutonium parts [RF-P084]

Fixer solution Radiographic film development [RF-P084]

Fluorescent dye Inspection and testing of plutonium parts [RF-P084]

Helium Pressure testing [RF-P084]

Liquid nitrogen Leak testing [RF-P084]

Metal cleaner; unspecified Cleaning bell jars after brazing [RF-P084]

Potassium hydroxide Used in compressors during pressure testing [RF-P084]

4-33


Between 1962 and 1965, expansion and changes occurred to some of the recovery processes in

Building 771 that allowed for substantial increase in production rates for plutonium recovery [RF-P091].
Although the molten salt extraction (MSE) process was developed in Building 771, the production
furnaces were located in Building 776. The addition of dissolution lines, filtrate recover, batching,
calcination and fluorination operations allowed for an increase in plutonium recycling production. The
various recovery processes available (i.e., the slow and fast cycle recoveries and later MSE in

Building 776) allowed plant operators to select the optimal recovery technology for residues bearing
plutonium above the EDL.

. Waste generating operations in Building 771 included plutonium part fabrication, plutonium

recovery, plutonium purification, anion exchange processing, chemical recovery, americium recovery,
and various support activities, as follows:

Plutonium part fabrication in Building 771 included foundry, casting, machining, coating,
inspection and testing, radiography, holding, and shipping. Plutonium casting and machining
operations generated the following line-generated residues: casting skull; split copper molds;
drybox gloves; worn or obsolete equipment; cutting oil and solvent; glovebox filters; CWS filters;

.. combustible materials such as paper, plastic, and rags; and spent.cutting. oil and solvent. These... —_.-

residues were processed through the recovery processes on the north side of the facility. The spent
cutting oil and solvent were drummed, originally for shipment and later for storage [RF-C055,
RF-P047, RF-P085, RF-P091, RF-P108, RF-P265].

Recovery operations in Building 771 focused on recovery of fissionable radioisotopes. The
plutonium recovery and purification process is illustrated in Figure 4-4. The recovery operations
were composed of essentially two processes termed the fast recycle or fast side process and slow
recycle or slow side process [RF-P084, RF-P085, RF-P091, RF-P099, RF-P103, RF-P108, RF-
P116, RF-P162, RF-P262, RF-P264, RF-U157].

The feed to the fast recycle process was residues having high plutonium concentrations, such as
casting skull, impure metal, plutonium oxide, and site-return plutonium metal. The materials were
dissolved in a series of dissolution steps and treated to produce a final plutonium metal “button.”
Recovery liquid wastes generated by fast cycle recovery were either transferred over to slow cycle
recovery or sent to Building 774 for treatment, provided sampling of the liquid wastes
demonstrated that radioactivity concentrations were within acceptable levels for release and
subsequent treatment.

Slow recycle recovery operations involved different types of processes depending on the nature of
the feed wastes to be handled. Examples of the feed waste used in the slow cycle process are:

- Metal contaminated with plutonium was processed through a metal leach process.

- Combustible residues except glovebox gloves, graphite molds, and used ion exchange resin
were incinerated to reduce the volume and convert the plutonium to an oxide.

- The incinerator ash, some graphite, graphite scarfings, incinerator firebrick scarfings, SS&C,
insulation, tantalum, glass, and filter sludge were leached with a nitric-hydrofluoric acid
mixture.


4.19.2 Chemical Constituents

Table 4-55. Chemicals used in Building 991.

A variety of chemicals were used in Building 991 that might be present in the wastes. These
chemical contaminants are listed in Table 4-55.

Constituent Generator/Process/Use Gf known)
Organic Compounds
140-66 solvent Nonplutonium physical metallurgy process [RF-P084]
2,2,2-trifluoroethanol Nonplutonium physical metallurgy process [RF-P084]
2-butoxyethanol Nonplutonium physical metallurgy process [RF-P084]

3-methylcyclohexanol
Acetone
—Aleohols__
Butyl lactate
Diacetone

Diglyme bis (2-methoxylethy]) ether

Dodecane

Ethyl acetate

Freon 12 or 22
Glue/adhesives

Hexane

Hexanol

Isopropyl alcohol
Lubribrand A

Methyl acetonacetate
Oakite

Octanol

Oil; lubricant

Oil; machining

Organic solvents; unspecified
Oxalic acid

Paint

Polychlorinated biphenyls
Tetradecane
Trichloroethylene

Nonplutonium physical metallurgy process [RF-P084]
Final assembly [RF-P084]
Alarm maintenance [RF-P084] a

Nonplutonium physical metallurgy process [RF-P084]
Nonplutonium physical metallurgy process [RF-P084]
Nonplutonium physical metallurgy process [RF-P085]
Nonplutonium physical metallurgy process [RF-P084]
Nonplutonium physical metallurgy process [RF-P084]
Utilities and maintenance [RF-P084]

Shipping and receiving, alarm maintenance
Nonplutonium physical metallurgy process [RF-P084]
Nonplutonium physical metallurgy process [RF-P084]
Metallography laboratory [RF-P085]

Shipping and receiving [RF-P084, RF-P085]
Nonplutonium physical metallurgy process [RF-P084]
Inspection testing [RF-P084]

Nonplutonium physical metallurgy process [RF-P084]
Utilities and maintenance [RF-P084]

Nonplutonium physical metallurgy process [RF-P084]
Alarm maintenance [RF-P084]

Metallography lab [RF-P084]

Shipping and receiving [RF-P084, RF-P085]

Utilities and maintenance [RF-P084]

Nonplutonium physical metallurgy process [RF-P084]
Final assembly [RF-P084] :

4-92


Table 4-13. (continued).

Constituent Generator/Process/Use (if known)
Hydrochloric acid Production plating [RF-P084]
Hydrogen peroxide Acid etching, solution mixture, nitric acid, hydrogen
peroxide, deionized water [RF-P085]
Lithium carbonate Heat treating [RF-C502]
Mac Stop (toluene, xylene, and Production plating [RF-P084]
nickel chloride mixture) .
Magnaflux No.1 Gray Powder Photo processing chemical [RF-C215]
Molykote (molybdenum sulfide) Unknown

Nitric acid

Metal etching and plating operations [RF-P085]

Oakite 162 Nonchlorinated solvent-chemistry technology [RF-U208]

Penetrant, Zyglo (DP-50) Photo processing chemical [RF-C215]

Phosphoric acid Physical metallurgy [RF-P085]

Potassium carbonate Heat treating [RF-C502]

Potassium cyanide solutions Plating [RF-C502]

Silicone Unknown—chemical inventory [RF-C215]

Sodium cyanide solutions Plating [RF-C502]

Sodium hydroxide Unknown—chemical inventory [RF-P085]

Sulfur hexafluoride Unknown—chemical inventory [RF-P085]

Sulfuric acid Physical metallurgy [RF-P085]

Terry Cleaner Unknown

Texaco CX Petroleum-based water soluble coolant [RF-P084]

Trim Rinse detergent Nonchlorinated solvent chemistry technology [RF-P084]

ZC-79 Used to clean Magnaflux No.1 Gray Powder from parts
[RF-C215]

ZP-9

Photo processing chemical [RF-C215]

4.5.3 Radionuclides

Building 444 conducted nonplutonium operations that generated radioactive, LLW. The only
radiological contamination related to the Building 444 wastes shipped to the INEEL is DU (Table 4-14),
From 1954 until April 1978, these wastes were included in shipments of plutonium-contaminated wastes
shipped to the INEEL for disposal [RF-P047].

4-19


Table 4-13. (continued).

Developer; Kodak

Developer rack cleaner (sodium

thiosulfate and sodium ferricyanide)

Developer system cleaner
Developer, Zyglo (ZP-5)
Dubl-Chek
Duo Seal

* Emulsifier, Zyglo (DP-50)
Enmulsifier, Zyglo (ZE-2)
GS-3

Constituent Generator/Process/Use (if known)
Beryllium : Physical metallurgy [RF-P085}
Brass Physical metallurgy [RF-P085]
Cadmium Physical metallurgy and electroplating [RF-P085]
Chromium Physical metallurgy [RF-P085]
Copper Physical metallurgy [RF-P085]
Gold Parts, casting, or alloy [RF-P085}
Lead (lead fluoroborate and lead Physical metallurgy [RF-P085]
oxide)
Mercury Physical metallurgy [RF-P085]
Molybdenum Used as a lubricant during assembly testing [RF-P084]
Nickel Parts, casting, or alloy [RF-P085]
Niobium Uranium alloy processing [RF-~C502]
Silver Physical metallurgy [RF-P084]
Magnesium Physical metallurgy [RF-P085]
Titanium Parts, casting, or alloy [RF-P085]
Tungsten Manufacturing [RF-P084]
Vanadium Physical metallurgy [RF-P085]
Yttrium oxide Coating beryllium molds [RF-P084, RF-U115]
Other Chemicals/Constituents
Ammonium hydroxide Uranium neutralization and precipitation from acid
solutions [RF-P084]
Calcium fluoride Coating beryllium molds [RF-U115]
Cimcool Coolant used in.DU machining [RF-P084]
Cyanide Heat treating and electroplating [RF-~C502]

Photo processing chemical [RF-C215]
Used photo processing chemical [RF-C215]

Photo processing chemical [RF-C215]
Photo processing chemical [RF-C215]
Photo processing chemical [RF-C215]
Unknown

Photo processing chemical [RF-C215] -
Photo processing chemical [RF-C215]
Photo processing chemical [RF-C215]

4-18


4.11.3 Radionuclides

Waste treatment operations in Building 774 produced all liquid process wastes generated in
Building 771 plus all other plant liquid process wastes that did not meet the requirements for offsite
release. Radioactive contaminants in the liquids thus reflected all radionuclides that could be present at
the RFP and included EU, DU, plutonium, small amounts of americium, and trace amounts of Cm,
*INp, and TM°U from R&D, production, and processing areas. The radionuclides that may be present in
wastes generated from Building 774 are listed in Table 4-34 [RF-P260, RF-P264]. ‘

Table 4-34, Radioisotopes present in Building 774 wastes [RF-P260, RF-P264].

Radionuclides
Plutonium ee, Am
DU EU
By 240m

ang . Loe _

Seventy (70) g of "Am a month was present in the waste stream sent for waste treatment in the
late 1960s because the americium recovery line in Building 771 did not have the capability to recover all
of the americium that was present in the waste stream. This americium would be captured in the
741 sludge. The amount of americium in the Building 774 series 741 sludge in fiscal year 1969 was
4.8755 kg. In April 1969, a-significant increase in gamma radiation dose was noticed for some of the
Building 774 personnel as a result of an increase in Am content in the waste sludge. In January 1970, a
gamma detector was installed in the first stage drum filter in Building 774 to help protect against
“surprise” processing of americium-rich sludges [RF-U128, RF-U135, RF-U157]. :

4.12 Buildings 776 and 777 '

Buildings 776 and 777 are a combined complex (referred to as Building 776/777), sharing a
common wall, utilities, and maintenance, that was completed in 1957 to accommodate plutonium
technological changes and designs. In the late 1950s, a change in the weapon concept occurred, which
resulted in an increase in plutonium relative to uranium content, In addition, different shapes of ‘plutonium
with closer dimensional tolerances were also required. This required more rolling, forming, and
machining of plutonium than in the earlier years of production [RF-P047, RF-P084, RF-U015].

These facilities contain foundry, machining, plutonium storage, and.assembly operations
[RF-P116]. As a result of the new construction and expansion of the C-Plant (Building 771), and the 1957
fire in Building 771, the plutonium foundry and machining operations were transferred to Building 776
from Building 771 in 1958. Likewise, the assembly and certification operations were transferred to
Building 777 from Building 991 [RF-P047, RF-P084, RF-U115].

The mission of Building 776 was plutonium components manufacturing, including casting and
plutonium parts fabrication from 1958 through 1969. This building was the main manufacturing facility
for plutonium weapons components. The production pyrochemical operation was also located in
Building 776 and the operation was expanded in 1967 to accommodate the MSE process. The MSE
process was used to remove americium, ahd the spent pyrochemical salts were used as the feed source for
the americium purification process [RF-P084, RF-P085, RF-U115]. The mission of Building 777 was

4-62


4.8.3 Radionuclides

The primary radionuclides that may be present in waste generated from Building 559 processes
include plutonium, americium, uranium, and neptunium, as well as ingrowths and daughter products
[RF-P094, RF-P085]. Radioisotopic content for individual wastes or RFP buildings cannot be determined.
A detailed discussion of radionuclide content in the RFP wastes is presented in Section 7.

4.9 Building 707

Building 707 construction began in 1967 to support production of the Part V weapons design that
could not be accomplished in Building 776 and 777; however, after the 1969 fire in Building 776 and
777, the plutonium foundry, casting, and machining operations for the Part IV design that were involved
in the fired-damaged areas of 776 became part of the operations in Building 707. The Building 707 Annex
(sometimes referred to as Building 707A) was constructed to accommodate all of the Building 776 and
777 operations that needed to be moved to Building 707 (RF-P084, RF-P085].

Plutonium manufacturing operations began on May 25, 1970. Beginning in 1970, Building 707
provided metallurgical support for plutonium and was involved in final product assembly. Plutonium
metal was cast into ingots in the foundry. The ingots were then rolled and formed prior to being
machined, cleaned, and assembled in various areas within the building. Once construction of
Building 707 was completed, the majority of plutonium pit assembly operations were moved from
Building 777 [RF-P084].

It is not known how many of the casting, fabrication, and assembly processes were operating at the
time waste was shipped to the INEEL from Building 707 (October 1970) as shown in the WILD
[RF-U1070] so these processes are briefly described below.

° Casting operations focused on production of feed and production ingots. The ingots were produced
from blending plutonium from various Building 771 sources and/or rejected parts. Final
gallium-stabilized WR ingots were then produced by blending feed ingots of known purity and
composition. Casting operations were performed in several modules within Building 707. The
processes employed in each module differed, mostly in the physical form of the starting materials
used [RF-P084].

. After casting, the molded parts underwent a series of fabrication steps to produce the final shape.
These steps included rolling, forming, thermal treatment, and final machining. Production ingots
were rolled until a specified thickness was obtained. These were moved to another glovebox where
shapes were cut out of the sheet in a blanking press. The cut blanks were sent to nearby gloveboxes .
for thermal treatment (annealing and homogenizing). After thermal treatment, the blanks were
formed into hemishells in a hydroform press. Final machining on the bulk plutonium parts was
conducted within various gloveboxes containing lathes, mills, a drillbox, and a high-precision drill
press [RF-P084].

. Machined parts went through a series of cleaning and assembly steps to produce the final
plutonium pit; the steps varied depending on the design of the pit (Part IV or V design) but were
usually iterative. After cleaning in an ultrasonic cleaner, plutonium parts were welded with electron
beam welders as part of the subassembly. An outer metal casing was welded onto the plutonium
subassembly with a pigma or electron beam welder in the “Superdry” process. Some metals parts
were joined using a process called electron bombardment brazing in which a nonferrous alloy was
used that melted at a lower temperature than the metals being joined. Building 707 also housed a

4-30


Table 4-42. (continued).

Constituent Generator/Process/Use (if known)
Trichlorotrifluoroethane Laboratory use [RF-C214]
Winterfene disinfectant Unknown—chemical inventory [RF-C215]

Metals

Aluminum oxide Unknown—chemical inventory [RF-C227]
Beryllium Unknown—chemical inventory [RF-C227]
Cadmium EU recovery [RF-P084] ;
Cadmium oxide Unknown—chemical inventory [RF-C227]

Chromium (includes chromium
trioxide)
Lithium '
Magnesium oxide

Other Chemicals/Constituents
Aluminum nitrate — . -
Ammonia gas
Ammonium bifluoride
Ammonium hydroxide
Boric acid
Copper sulfate
Cyanide plating solution
Helium
Hydrazine
Hydrofluoric acid (HF-H.)
Hydrogen peroxide 30%
Magnesium zirconate
Nitric acid
Potassium chloride
Potassium hydroxide
Sodium bicarbonate
Sodium hydroxide
Uranyl nitrate

Unknown—chemical inventory [RF-C227]

EU recovery [RF-P064, RF-P084]
Unknown—chemical inventory [RF-C227]

Unknown—chemical inventory [RF-C227] — —
EU recovery [RF-P084]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Plating operations [RF-C420, RF-P260]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
EU recovery [RF-P084]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
Unknown—chemical inventory [RF-C227]
EU recovery [RF-P084]

4.14.3 Radionuclides

The radioisotopes that may be present in waste generated from Building 881 are listed in

Table 4-43; however, specific concentrations of each isotope are unknown [RF-P064, RF-P084]. EU
production started in 1953. Beginning in 1964, EU work was curtailed in Building 881 and 883 as the

RFP mission of producing EU components was transferred to the Oak Ridge Y-12 Plant. Limited

operations associated with shut down and cleanup of residual EU in Building 881 continued through 1967
[RF-P084, RF-P105]. Some radionuclide traces and other radioisotopes were used in Building 881 for


ENERGY EMPLOYEES
COMPENSATION RESOURCE CENTER

December 16, 2013

Enclosed are your copies of paperwork submitted under the Energy Employees
Occupational Illness Compensation Program (EEOICPA).

The original paperwork was forwarded to your assigned Claims Examiner at the
appropriate Department of Labor District Office for inclusion in your EEOJCPA case
file. :

Keep these copies in a safe place as copies are not kept in the Resource Center.

Please do not hesitate to call if you have questions. I can be reached at 1-866-540-4977
(toll-free) or 720-540-4977.

Sincerely,

Enclosures:
As stated

8758 Wolff Court, Suite 101, Westminster, CO 80031
Phone 720-540-4977 and 1-866-540-4977 (toll-free) fax: 720-540-4976
denver.center@rrohio.com


. 4.10.2 Chemical Constituents
Because of the wide range of operations conducted, a variety of chemicals may be present in the
waste shipped from Building 771. A list of chemicals used in the building, and the processes in which
they were used, is provided in Table 4-24.

Table 4-24. Chemicals used in Building 771.

Constituent Generator/Process/Use (if known)
Organic Compounds
1,1,1-Trichloroethane Product R&D [RF-P100, RF-P241]
2-ethyleneoxyethanol Plutonium metallurgical R&D [RF-U217]
Acetic acid Plutonium metallurgical R&D
Acetone Plutonium metallurgical R&D, analytical and mass
. Spectrometry laboratories (until 1967) [RF-P084,
. RF-U117, RF-U202] : --
* Alcohol Plutonium metallurgical R&D [RF-PO84]
Alcohol; denatured Peroxide precipitation [RF-P084]
Ammonium thiocyanate Americium precipitation, Building 771 analytical
laboratory [RF-C205, RF-C502, RF-P085, RF-P260]
Benzene Radiation instrument group (until July, 1956) [RF-U182]
Bromobenzene Density determination of plutonium metal buttons
[RF-C502]
Carbon Plutonium metallurgical R&D [RF-P084]
Carbon tetrachloride Plutonium machining, plutonium metallurgical R&D,

product R&D, analytical and mass spectrometry
laboratories, chemistry R&D [RF-P137, RF-P187,
RF-U117, RF-U201, RF-U202]

Chloroform Analytical and mass spectrometry laboratories (after
1967) [RF-C214, RF-P084]

Dibuty] butyl phosphonate Building 771 analytical laboratory [RF-C502]

Dodecane Uranium-plutonium solvent extraction [RF-P091]

Ethylene glycol Plutonium metallurgical R&D [RF-U217]

Freon 113 Density balance [RF-P084]

Freon 12 Refrigeration [RF-P084]

Hexane (cyclohexane) Analytical laboratory [RF-P084]

Isopropyl alcohol Plutonium metallurgical R&D; ‘aboratory, peroxide
. precipitation [RF-P084]

Oils: machining, coolant, and Plutonium machining, plant operations, plutonium

vacuum pump metallurgical R&D, product R&D, chemistry R&D

[RF-P084, RF-P100, RF-U133]


4.9.3 Radionuclides

Weapons grade plutonium, EU, and DU were commonly used in the Building 776 and 777
processes, and many of the same processes were continued in Building 707. It was assumed that the same
radioisotopes are present in Building 707 wastes in the same ratios. The radioisotopes that may be present
in Building 707 wastes are listed in Table 4-22. Radioisotopic content for individual wastes or specific to
the RFP buildings cannot be determined; however, radioisotopic content for all of the RFP waste was
estimated and is discussed in detail in Section 7.

Table 4-22. Radioisotopes expected to be present in Building 707 wastes [RF-P084, RF-P085, RF-U1 15].

Radionuclides
21am 2INp
2Bepy 24Ipy
23py my
| py 25y
2p 238

4.10 Building 771

Building 771 (originally referred to as the C-Plant or Building 71) was constructed and placed into
operation in 1953. It was designed as a totally self-contained plutonium production facility to provide
plutonium component manufacturing, plutonium recovery, and plutonium purification [RF-P047,
RF-P084, RF-P085, RF-P091, RF-P260, RF-P262, RF-P264]. All fabrication of plutonium components
was conducted in Building 771 from 1953 until 1957 when plutonium fabrication and component
assembly operations were moved to Building 776/777. From 1954 to 1958, Building 771 had its own
laundry facility. At that time, all laundry operations for plutonium-related buildings was moved to
Building 778 [RF-P085, RF-U115]. By the mid-1950s, increasing complexity of the plutonium part
fabrication processes necessitated the construction of a dedicated plutonium fabrication facility,
Building 776 (originally Building 76). A large plutonium casting residue fire occurred in the development
laboratory on September 11 and 12, 1957, which seriously contaminated the metals laboratory and most
of Building 771 [RF-P047, RF-P085, RF-P091, RF-P108, RF-P265].

Renovation of Building 771 included removal of the original production line beginning in late 1958
or early 1959, and was completed by 1962.

In 1957, the primary mission of Building 771 became plutonium recovery and purification
[RF-P047, RF-P084, RF-P085, RF-P091, RF-P260, RF-P262, RF-P264]. Recovery operations in
Building 771 included recovery of fissionable radioisotopes as well as recovery of solvents for reuse.
Early recovery operations were conducted in gloveboxes and consisted of simple manually operated
equipment. By 1957, a small incinerator located in Building 771 was used to reduce the bulk of
combustible waste materials by incineration. A larger incinerator and off-gas system replaced the original
incinerator in 1961. The combustion was sometimes incomplete in bath incinerators. In the small
incinerator and the first few runs of the larger incinerator, the feed to the incinerator was anything that
would burn. This included PVC plastic, polyethylene, rubber (glovebox) gloves, paper, some graphite,
rags, wood, and ion exchange resins. Later, glovebox gloves and PVC plastic were excluded because they
caused plugging of the filters and equipment corrosion [RF-P107, RF-P162, RF-U114].

4-34


Table D-40. U.S. Geological Survey waste types by year of shipment.
US. Geological Survey (USGS) Waste Types

Volume (cubic fest)
Combustibte!
Non- Beryllium
Year of Combustible Non- Filter Paper Sludge Waste| ' OiWvOrganic
Shipment | Debris(}) | Combustible Ww Filters (i) (M) Combustible Sludge (vi) [Contaminated
Debris (LV) : ebris (Vv) Debris (vil)
7954 0 0 0 ° 0 7 0 3
1955 0 0 0 0 0 0 0 0
1956 0 0 0 0 a 0 0 t)
1987 0 0 0 0 0 0 ° 0
1958 9 0 0 0 ° 0 0 0
1959 0 0 ° 0 ° 0 0 0
1960 0 0 0 0 0 0 0 °
4961 0 0 ° 0 0 8 0 0
1962 0 0 0 0 0 0 0 0
1963 0 0 0 0 0 0 0 0
1964 ° 0 0 0 0 0 0 0
1965 7 0 0 0 ° Q 0 0
1966 0 e 0 0 0 7 0 0
1987 0 7 0 Q 0 15 ° 0
eee —-—| 1988 ~—] ——-0-~—| 9} 0 —-]}--—~9-——- 1} -—6 Ta m—9. 0
1969 0 68 0 0 0 0 0 0
1970 0 68 0 0 0 0 0 0
TOTAL (7) 7 739 ° 0 2 2 ° 0
A chart was not creatad for this building due to the small volume of waste andlor few waste types
Table D-41. Total RFP waste by year of shipment.
‘Total RFP Wastes (Including Dow") .
Volume {cube fal)
Combustible! Non- Beryllium. 23 ua |
Nearof [Combustible | Non | Fateh sper | ritors cay pS a28e M8t0) combucstinte | OMOTUENC |e, saminated| Contaminated] Contaminated]
Shipment | Debris (}) Combunt aw a w Dabris(v) | 40° “Submis (va) | Suapeiny | Deose tw
1954 8554 34 o 0 ‘8827 ‘$873 0 oO o °
1955 14924 ‘2803 78 5502 7103 624 o o oO 0
1886 17008 73 764 1026 ‘S365 ‘9849 0 oO o o
41957 26749 3363 4663 ‘8608 9384 17880 274 0 o o
1958 (26221 1497 OT 4424 ‘7a87 15445, 429 102 oO o
1859 (38769 483 368 T28T 9138 ‘21628 o 307 o 0
1960 20362 ‘6247 380 476 10506 20878 a8 1078 o o
4861 33388 7384 788 8005 10594 28308 160 200 ° oO
1962 44581 38T ral) 2937 14140 (35529 153 1494 ° o
1963, 63182 148 154 5713, 11707 45136 65 4680 0 o
1964 ‘58367 $72 o BES6 864g S11TO o ‘3748 o o
1955, ‘41240 1047 7 ‘5335 429 60282, 0 3299 7 418
1986 A2036 35653 313 14077 17888 ‘55285 675 3628 o 139
4967 ‘23874 39224 419 11464, 21895 76878 38828 1028 oO o
1968 26952 161588 1831 ‘7423 42222 73928 (28637 514 0 15
1963 7313 149499 4207 8386 31769 (28286 ‘5561 2035 ° o
1070 29 212227 4648 3874s 28046 5129 8728 Sat o o
TOTAL (f°) 492420, 615725 17996 133070 253121 ‘564870 81549 21804 7 STZ

* Wastes designated under the RFODOW generator have been included because Il is belived the majority of this waste is RFP waste.

D-44


Table 4-56. Radionuclides expected to be present in Building 991 [RF-P041].

Radionuclides
241 ‘Am 22py
238Dy B5Uy
235py 2381
Py ball
2Ipy Boy

4:20 Building 995

Building 995 was originally constructed in 1953 as the main structure supporting the sanitary sewer
"system at the RFP and has served that function since then, The building has two additions since 1953. The
first, built in the late 1980s, housed upgraded monitoring instrumentation and increased the size of the
onsite laboratoryThe second;-built in the-mid-1990s; provided an-additional-onsite laboratory; office
space, and restroom facilities [RF-P096].

4.20.1 Physical Waste Matrices Generated

A total of 89 containers (574 ft*) were generated from activities conducted in Building 995. These
numbers were compiled from the WILD [RF-11070] and grouped into the seven waste types as described
in Section 3.4 and presented in Table 4-57. Appendix A contains a more detailed presentation of the
original waste type assignments entered into the WILD as well as delineation into the seven final waste
types. See Appendix D (Table D-27) for a timeline showing volume of waste by year shipped to the
INEEL as compiled from the WILD [RF-U1070].

Table 4-57. Waste volumes shipped to the INEEL designated 995 [RF-U1070].

Building 995, Sewage Treatment Plant

Waste Type Waste Description Container Count Volume (ft)
1 Combustibles 0 0
Tand V Combustibles and noncombustibles 47 265
I Filter paper 0 (0)
m0 Filters “0 0
Iv Inorganic sludges _ 42 309
v Noncombustibles 0 . o-
VI Organic wastes : 0
vol Beryllium-contaminated debris 0 : 0

Total 89 574

4-94


Table 4-55. (continued).

Constituent Generator/Process/Use (if known)
Trifluoroacetic anhydride Nonplutonium physical metallurgy process [RF-P084]
Trim Sol cutting oil Metallography lab [RF-P084]

Triple C Cleaner Shipping and receiving [RF-P084]
Ultrasonic coupling gel * Nondestructive testing [RF-P084]
Metals
Beryllium Final assembly [RF-P085]
DU Final assembly [RF-P085]
EU Final assembly [RF-P085]
Lead (paints) Utilities and maintenance, alarm maintenance [RF-P084,
RF-P085]
Plutonium Final assembly [RF-P085]
Other Chemicals/Constituents
Acids; unspecified Alarm maintenance [RF-P084]
Alumina grinding paper Metallography lab [RF-P084]
Developer solutions and cleaner Nondestructive testing [RF-P084]
Diamond paste Metallography lab [RF-P084]
Dye penetrant Nondestructive testing [RF-P084]
Dye penetrant cleaner Nondestructive testing [RF-P084]
Film Nondestructive testing [RF-P084]
Fluorescent light bulbs Utilities and maintenance [RF-P084]
Hydrochloric acid Metallography lab [RF-P084]

" Nitric acid Metallography lab [RF-P084]
Phosphoric acid Metallography lab [RF-P084]
Photographic fixer Nondestructive testing [RF-P084]
Polishing solutions, nonhazardous Metallography lab [RF-P084]
Silicon carbide grinding paper Metallography lab [RF-P084]
Sodium bicarbonate Shipping and receiving [RF-P084, RF-P085]

4.19.3 Radionucildes
The radioisotopes that may be present in wastes generated in Building 991 processes are listed in

Table 4-56. Radioisotopic content for individual wastes or specific to the RFP buildings cannot be
determined; however, radioisotopic content for all RFP waste is discussed in detail in Section 7.

4-93


4.8.2. Chemical Constituents

Chemicals used in laboratory processes conducted in Building 559 may be present as waste
contaminants generated in Building 559 and are listed in Table 4-19.

Table 4-19. Chemicals used in Building 559.

Constituent Generator/Process/Usé (if known)
Organic Compounds
1,1,1-trichloroethane Laboratory [RF-P085]
Dibuty] butyl phosphonate Laboratory [RF-C502]
Carbon tetrachloride Laboratory [RF-P085]
Chloroform Laboratory [RF-P085]
Ethanolamine Laboratory [RF-C502]
Formaldehyde . _. Laboratory [RF-P085]
Methylene chloride Laboratory [RF-P085]
Tetrachloroethylene Laboratory [RF-P085]
Thenoyl trifluoroacetone Laboratory [RF-C502]
Tributyl phosphate Laboratory [RF-C502]
Trioctyl phospine oxide Laboratory [RF-C502]
Urea _ Laboratory [RF-C502]
Metals
Beryllium (oxide) Laboratory [RF-P085]

Chromium (chloride, nitrate, oxide, potassium Laboratory [RF-P085]
sulfate, sulfate, trioxide)

Gallium Laboratory [RF-C502]

Lead (acetate, chloride, metal nitrate, oxide, Laboratory [RF-P085]
powder)

Mercury (nitrate) Laboratory [RF-P085]
Nickel (powder, nickelous chloride, nitrate, Laboratory [RF-P085]
oxide, sulfate)

Other Chemicals/Constituents .
Acids and bases; unspecified Laboratory [RF-C205]
Nitric acid Laboratory [RF-P085]
Potassium dichromate Laboratory [RF-C502]

4-29


4.13.2 Chemical Constituents

A variety of chemicals were used in Building 779 processes that may be present in the wastes, as
shown in Table 4-39.

Table 4-39. Chemicals used in Building 779.

Constituent Generator/Process/Use (if known)

Organic Compounds

1,1,1-trichloroethane Chemistry technology [RF-P040]

Acetone* Unknown—chemical inventory [RF-C215]

Carbon tetrachloride Chemistry technology, physical metallurgy [RF-C223,

RF-P085, RF-U188]
Chloroform Chemistry technology [RF-P085]
Ethanol" Unknown — chemical inventory [RF-C215}
“Freon " Physical metallurgy [RF-P040]

Kerosene Unknown—chemical inventory [RF-C215]

Methylene chloride Physical metallurgy [RF-P040]

Oil; lubricant and coolant Physical metallurgy [RF-C223]

Oil; silicone Unknown—chemical inventory [RF-C215]

Oxalic acid Physical metallurgy, joining and coatings [RF-P040]

Trichloroethylene* Unknown—chemical inventory [RF-C215]

Xylene* Unknown—chemical inventory [RF-C215]
Metals

Chromium Chemistry technology, physical metallurgy [RF-P085,

RF-U208]}

Lead Unknown [RF-P085]

Mercury Unknown—chemical inventory [RF-C215]

Silver Unknown—chemical inventory [RF-C215]
Other Chemicals/Constituents

Ammonium hydroxide Chemistry technology [RF-P040]

Calcium chloride Chemistry technology [RF-P040]

Copper sulfate Joining and coatings [RF-P040]

Dimethylamine Chemistry technology [RF-P040]

Hydrazine Chemistry technology [RF-P040, RF-P085]

Hydrochloric acid Chemistry technology [RF-P040, RF-U208]

Hydrofluoric acid Joining and coatings [RF-P040]

Lithium perchlorate Chemistry technology [RF-U208]

4-72


Table D-33. DOW Construction specific Type V and I,V wastes by year of shipment,
DOW Construction Specific Type V and |,V Wastes .
(Not included in Non-combustible or Combustible/Non-combustible debris tabulations)
Volume {cubic feet)

Line
Generated
Waste (1,V)

Year of Empty Drums
Shipment (vy)

1954
1955
1956
1957
1958

* [Roaster Oxide]
eae

eoeoagocod

1966
1967
1968
1969
1970

SCOCOCCRAGCDOCCCOCCOO SR

8
ecogcoeoeecc OCC CSD

2
eogocnce
a
2
N

°

TOTAL (ft’) 665 132 4417

D-39


‘quouadnys Jo reek fq saysem A‘] pue A addy oytosds uononnsuop MO ‘Si-c eNsLy

[(A) epixo siseoy” | (n'1) a1SeM Payesoued eur] —w- (A) swing Adwig—o—|

juauidyys jo 329,

aoz-

00z

OOP

009

* 9993 91QN9) eUIN|OA

008

0001

(suopeinge; sige

o0zL

P BIGHSNqUIOS-UON/aIqHSNqWIOD Jo B1qRSNQuIOS-LON Uy Papnjaul JON)
SajseM A‘] pue a adAy oyioeds uojondjsucg MOG

‘D-40


mCi

MLLW

-MOCA

mrem/hr
MS
MSE
MTD

MTC

NOL
NRTS
ORNL
PCB
PCE
ppb
ppm
Pvc

molar

meter

cubic meter

mega curie

mixed-low-level waste
millimeter
4,4-methylene-bis(2-chloraniline)
millirem

mill roentgen per hour

millirem per hour

Material Status

molten salt extraction

empty drum (used on the empty contaminated lathe coolant [oil] drums)
empty container

impure materials contaminated with EU ground to a fine powder for nitric acid leaching (the
nitric acid solution was filtered and the solids collected from the process were called MUD)

material unaccounted for
nondestructive assay

normal operating loss

National Reactor Testing Station

Oak Ridge National Laboratory
polychlorinated biphenyl
tetrachloroethylene (perchloroethylene)
parts per billion

parts per million

polyvinyl chloride

research and development

ix


4.2.4 Radionuclides

The radioisotopes that may be present in wastes generated from Building 123 processes include
actinide elements, compounds, sources, and other radioactive materials historically used at the RFP
including, but not limited to, the isotopes and radioactive decay products listed in Table 4-6. Radioactive
spike solutions were used as additives during preparation of most samples, and radioisotopic sources were
used in the determination of contamination as part of the normal operating health physics procedures
associated with Building 123. Large plutonium/beryllium neutron sources were disposed of from this
building in 1972. The sources were sealed in a produce can, placed in DOT 6M containers, and then
placed in a drum with plutonium-contaminated LGW [RF-C138]. Although this occurred after the time of
waste disposal at the INEEL addressed by this report, it is assumed that similar radioactive sources from
Building 123 could have been disposed of at the INEEL previously. Radioisotopic content for individual
wastes or wastes specific to RFP buildings cannot be determined. Radioisotopic content for all RFP waste
is discussed in detail in Section 7 [RF-P181]},

Table 4-6. List of radionuclides for the RFP site as potential contaminants-——Building 123 [RFPI8 1}.

Radionuclides

Am °Ni Ms,
Ba 210py aay
25006 236py 23517
Mom 29py 236qy
Blas 240py 238
3y py : _
8Gq py _

4.3 Building 331

Building 331 was built in 1953 as a vehicle maintenance garage and the RFP fire department. The
building also housed a smali metallurgical R&D laboratory [RF-P065].

4.3.1 Building 331 Waste Generating Operations

Waste from Building 331 was primarily generated by the decontamination of fire fighting
equipment and vehicles (on the vehicle maintenance side) that were contaminated with plutonium,
uranium, or other radioactive materials handled during operations at the REP.

A small R&D laboratory also housed in this building was engaged in evaluating equipment and

methods applicable to casting and fabricating DU items. A limited thorium project was also conducted in
this facility [RF-U115].

4-6


Table 4-24. (continued).

Constituent Generator/Process/Use (if known)

Hydroxylamine nitrate Neptunium anion exchange, neptunium precipitation
[RF-P260]

Hydroxylamine sulfate Solvent extraction [RF-P264]

Todine * Thermite reduction [RF-P260]

Magnesia cement Waste packaging [RF-U288]

Magnesium chloride MSE (B776) [RF-P260]

Magnesium granules Thermite reduction [RF-C502]

Magnesium perchlorate/sulfuric acid Laboratory scrubber [RF-P091]

mixture

Nickel carbonyl Nickel plating (to at least 1963) [RF-P047, RF-U042,

: RF-U046] ,

Nitric acid Dissolution, calciner scrubber, anion exchange, batching,
peroxide precipitation, americium recovery [RF-P084,
RF-P085, RF-P091, RF-P260]

Nitrous oxide Analytical laboratory [RF-P084, RF-P091]

Perchloric acid Laboratory [RF-U208]

Phosphoric acid Plutonium metallurgical R&D [RF-U201]

Potassium hydroxide Anion exchange, americium recovery [RF-P084,
RF-P260]

Potassium iodate Thermite reduction [RF-P084]

Sodium fluoride Fluidized-bed fluorinator [RF-P264]

Sodium hydroxide Solvent extraction, peroxide precipitation [RF-P084,
RF-P108, RF-P260]

Sodium peroxide Thenmite reduction [RF-P084]

Sulfamic acid Solvent extraction, dissolution [RF-P264]

Sulfuric acid Peroxide precipitation; neptunium dissolution [RF-P084]

4-48


Table 4-32. Waste volumes shipped to INEBL designated 746 [RF-U1070].
746 Empty Contaminated Drums and Associated Waste

Waste Type Waste Description Container Count Volume (ft?)

I Combustibles 159 18,796
IandV Combustibles and noncombustibles 578 12,521
I Filter paper 0 0
pit Filters 1 185
Iv Inorganic sludges 0 0
Vv Noncombustibles 5,211 59,461
VI Organic wastes 0 0
VI Beryllium-contaminated debris 3 22

Tofal 5,952 90,985

4.11.2 Chemical Constituents

Building 774 was a waste treatment facility responsible for treating liquid wastes generated at the
RFP. The wastes generated from this building may contain any of the chemicals used across the site as
well as the chemicals used to treat (solidify) the liquids. A list of chemicals used is provided in each
building section. The list of chemical reagents used in the Building 774 first- and Second Stage Sludge
processes is provided in Table 4-33. A comprehensive list of chemicals used at the RFP during the 1954
to 1971 time frame has been included in Section 6.

For 743 sludge, Cab-O-Sil was used initially in the preproduction runs of the stabilization process,
but did not work well with the equipment in place. Use of Cab-O-Sil was then replaced by
Johns-Manville Microcel E calcium silicate. The majority of the organic sludge waste produced was
solidified using Microcel E [RF-C015, RF-P047, RF-U115]. In 744 sludge, liquid wastes requiring
neutralization were neutralized using caustic soda, lime, sodium hydroxide, or potassium hydroxide.
[RF-P047, RF-U115].

Beginning in the 1930s, PCBs were used for industrial purposes and were not regulated until after
the Toxic Substance Control Act was passed in 1976, Arochlor-1254 was used at the RFP for 15 years as
a vacuum pump and heat transfer fluid. In addition to debris waste containing low concentrations of PCBs
from paint, solidified PCB waste, oil, and motors and pumps containing PCBs (from the 1969 fire) were
all sent to the INEEL for disposal. It is also possible that PCB-contaminated oil could have been
processed with other organic liquid wastes and sent to the INEEL. Containers of ‘PCB-containing oils
such as transformer fluid were collected and stored with other oils until a treatment process became
available in 1966. Up to 5,000 drums of oil waste had been accumulated by that time. This waste was
processed through Building 774 as organic liquids beginning in August 1966 and shipped to the INEEL
as 743 sludge. Processing data collected from PCB wastes processed in later years indicate that the PCB
waste were combined with other wastes in the treatment process. Sampling and analysis data collected
from 1979 through 1986 for organic sludge wastes showed a UCL >50 ppm PCBs. The PCB
contamination was attributed (at least in part) to the inclusion of mineral oils in the feed waste to the
Building 774 treatment process. It is assumed that PCB-contaminated oils were processed in Building 774
prior to 1970 and are, therefore, a constituent of the 743 sludge waste. One of the large metal presses in


4.2.3 Chemical Constituents

The chemicals used in laboratory processes that may be present as contaminants of the waste
generated in Building 123 are listed in Table 4-5 [RF-P181].

Table 4-5. Chemicals used in Building 123.

Constituent Generator/Process/Use (if known)

Organic Compounds
Acetic acid Analytical processes [RF-P18]]
Acetone Analytical processes [RF-P181]
Ammonium thiocyanate Analytical processes [RF-P181]
Cyclohexane Analytical processes [RF-P181]
Ether : Analytical processes [RF-P181]
Ethylene glycol Analytical processes [RF-P181]
Isopropyl alcohol Analytical processes [RF-P181]
Methanol Analytical processes [RF-P181]
Oxalic acid Analytical processes [RF-P181]
Toluene Analytical processes [RF-P181]
Triisooctomine Analytical processes [RF-P181]
Xylenes - Analytical processes [RF-P181]
Metals .
Arsenic Analytical [RF-P181]
Beryllium Analytical [RF-P181]
Cadmium Analytical [RF-P181]
Chromium Analytical [RF-P181]
Lead Analytical [RF-P181]
Mercury Analytical [RF-P181]

ther Chemicals/Constituents
Ammonium hydroxide Analytical processes [RF-P181]
Formic acid Analytical processes [RF-P181]
Hydrochloric acid Analytical processes [RF-P181]
Hydrofluoric acid Analytical processes [RF-P181]
Nitric acid Analytical processes [RF-P181]
Perchloric acid Analytical processes [RF-P181]
Potassium permanganate Analytical processes [RF-P181]
Sodium hydroxide Analytical processes [RF-P181]
Sulfuric acid Analytical processes [RF-P181]

45


6r-d

Votume (cubic feet)

-Year of Shipment

== Combustible Debris (1) Combustible/Non-Combustible Debris (I,V)|- Filters (Il)

|x Sludge Waste (IV) —e— U233 Contaminated Sludge (IV) +-Non-Combustible Debris (V)
| ——oivOrganic Sludge (VI) : ——Berylium Contaminated Debris (VII)

Figure D-6, Volume of Building 774 waste types (including 74 studges) by year of shipment (Type V and I,V wastes do not include roaster oxide,
graphite, line generated waste, fire waste, and empty drums).


ACRONYMS AND ABBREVIATIONS
AEC Atomic Energy Commission
ANL-W = Argonne National Laboratory-West
AK acceptable knowledge
ARA-I Auxiliary Reactor Area-I

ATMX U.S. Department of Energy acronym used to denote the railroad cars used to ship waste from
the RFP to the INEEL

BOR United States Bureau of Reclamation
BWI Buried Waste Information

CBFO Carlsbad Field Office... -.--—..---- 0 -n--2eess

CH contact-handled
Ci curie
Cilg curies per gram

CFC chlorofluoro-hydrocarbon

CPC Coors Porcelain Company

CPR cellulosics, plastic, and rubber

CUM University of Colorado Medical Center
Cws Chemical Warfare Service

D-38 Tuballoy, a depleted uranium form with less of the fissionable *°U isotope than the
approximate 0.7 percent by weight found in natural uranium and rich in the “*U isotope

DOE Department of Energy
DOR direct oxide reduction

DOT Department of Transportation

Dow Dow Chemical Company
DRI Denver Research Institute
DU depleted uranium

EDL economic discard limit

vii


U.S. DEPARTMENT OF LABOR Employment Standards Administration

Office of Workers’ Compensation Programs
Division of Energy Employees’ Occupational
Mlness Compensation

November 22, 2013

Dear Mr.

Thank you for participating in the Occupational History interview. Your input will aid the Claims
Examiner at the DOL District Office in the development of your claim, The information gathered during
this interview will be used to develop the most up to date information regarding the possible exposures the
employee may have come into contact with while working at the Department of Energy’s site(s). It will
also provide the physicians who may be reviewing your case, or performing an evaluation, with a more
complete picture of the employee’s exposures, medical condition and history.

If you have any questions regarding the information gathered, or if you come upon other relevant
information you want shared with this program, please contact the District Office at:

(1 1-877-336-4272 DOL Jacksonville District Office
(C1 1-888-805-3401 DOL Seattle District Office
1-888-805-3389 DOL Denver District Office

(1 1-888-859-7211 DOL Cleveland District Office

Thanks again,



Table 4-12. Wastes generated from Building 444 activities [RF-U1070].

Building 444 A-Plant, DU, and Beryllium Metallurgy

Waste Type Waste Description Container Count Volume (f°)
I Combustibles 4,327 31,473
landV - Combustibles and noncombustibles 4,614 561
I Filter paper 1,008 182
cit Filters 1171 6,918
Iv Inorganic sludges 126 836
Vv Noncombustibles 10,878 95,610
VI Organic wastes 38 276
vu Beryllium-contaminated debris 2,517 20,526
Total ce a= 24,679 210481

Waste Type I consists of combustible debris including large quantities of sandpaper and emery

cloth; butcher paper used to cover worktables during coating; and other paper, plastic, and rubber
materials. To estimate the amount of CPR contained in the waste generated from Building 444 activities,
the following assumptions were made:

Because the Type I waste consists of combustibles including paper products, plastics, and rubber
items, the contents of the drums identified as Type J are assumed to be predominantly CPR.

‘Type Il filter paper is also combustible debris waste, as are the Type Hl CWS filters generated
prior to 1957; these are, therefore, CPR waste [RF-D001]. After the 1957 fire in Building 771, all
combustible-type CWS filters in all buildings across the RFP were replaced with fire-resistant

ters [RF-P265, RF-U057]. —

As a conservative measure, one half of the wastes identified under the combined J and V waste
types will be assumed to be Type I combustible debris and predominantly composed of CPR.
materials,

All aqueous and organic liquids and solid wastes generated in Building 444 were contaminated

with uranium and beryllium. Liquid wastes contaminated with uranium were sent to Building 774 for
processing, and solid debris wastes (Types I, I and V, Il, III, and V) were directly packaged as wastes.

Building 444 equipment and/or apparatus that moved air and/or displaced air had CWS and/or HEPA
filtering system(s), including furnace vacuum pump exhausts. The spent filters were contaminated with

beryllium or beryllium oxide and disposed of as Type I waste [RF-D001, RF-P084, RF-U115].

Metal bricks that were used to line the furnaces were contaminated with DU and were discarded as

‘Type V waste. Graphite molds were sent for cleaning to remove residual metal, powdered graphite, and

yttrium oxide. Wastes from the cleaning process were [RF-U115}:
. Graphite dust disposed of onsite in the RFP landfill.

. Spent graphite molds, generally disposed of as whole molds [RF-P105].

4-15


Table D-38. Sunstrand waste types by year of shipment.

‘Sunstrand (SUN) Waste Types

Volume (cubic feet)

Year of
‘Shipment

Combustible
Debris (1)

‘Combustiblel)
Non-
Combustible
Debris (1,V)

Filter Paper
aly

Filters (Ill)

Sludge Waste
TM

Non-
Combustible
Debris (V)

OWOrgantc
‘Sludge (Vi)

Beryllium
Contaminated!
Debris (vil)

1954
1955
1956
1957
1958
1959
1960
1964
1962
1963
1964
1965
1966
1967
| __—1968.

[}
oO
0
0
139
183
o

1969
1970

TOTAL (fr)

eloosccos ccc cC ecco ed

elooo oo De D OO OC OSC CSD

elooseeaccc ccc ese 000

elooscoeD ec DOD OOO OS

cloosc oc cece oo eCOeSD

Blooboooccce

jeloooecececeaec CO Oc oOScD

eloosececeon oe aoe COC Ce

A chart was not created for this building due to the small volume of waste and/or few waste types

Table D-39. The Oil Shale Corporation waste types by year of shipment.

The Oll Shale Corporation (TOSCO) Waste Types
Volume (cubic feet)

Year of
Shipment

Combustible
Debris (I)

‘Combustible!
Non-
Combustible
Debris (1,V)

Filter Paper

Filters (tl)

Sludge Waste!
(TM

Non-
Combustible
Debris (V)

‘OlWOrganic
Sludge (Vi)

Beryllium
Contaminated]
Debris (Vit)

1954
1955
1856
1957
1958
1959
1960
1961
1962
1963
1964
1965
1966
1987
19688
1969
1970

[TOTAL (fr)

OO ee

eloccccc oc ceca eoccea

elocoen cece DCDCDC OECD

elocccc eco eco GC eCOd

elocooc nce ee oCeCCOd

rr

Soe ee ee

A chart was not created for this bullding due to the small volume of waste and/or few waste types

D-43



RCRA Resource Conservation and Recovery Act
RFETS _ Rocky Flats Environmental Technology Site
RFP Rocky Flats Plant
RWMC _ Radioactive Waste Management Complex
* SDA Subsurface Disposal Area
SNM special nuclear material
SOM Colorado School of Mines
SRO Special Recovery Operation
SRWRT Solid Radioactive Waste Retrieval Test
" SS ~ > ‘spécial source —— —
SS&C sand, slag, and crucible
SSNM strategic special nuclear.material
SUN Sunstrand Manufacturing
TBP tributyl phosphate
TCA 1,1,1-trichloroethane
TCE trichloroethylene
TOSCO = The Oil Shale Company
TRU transuranic
USGS United States Geological Survey
VA Veterans Administration
Ww watt
WAC waste acceptance criteria
WILD Waste Information and Location Database
WIPP Waste Isolation Pilot Plant
WR War Reserve

wey weight percent


Table 4-24. (continued).

Blacosoly, Alk-Tri®, Ex-Tri®)

Trichlorotrifluoroethane (Genesolv
D®, Freon MF®, Freon TF®)

Trichlorotrifluoroethane-ethylene
glycol monobutyl ether mixture
(Freon TB-1®)

Thenoyl trifluoroacetone

Metals

Beryllium

Cadmium salts
Calcium metal
Calcium-zine alloy
Gallium

Magnesium oxide
Magnesium; powdered
Molybdenum

Nickel

Palladium

Silver

Constituent Generator/Process/Use (if known)
Oxalic acid Oxalate precipitation [RF-P085, RF-P260]
Perchloroethylene (Chlorothene®, Product R&D, chemistry R&D [RF-P100, RF-P187]
Chlorothene NU®, Chlorothene

_ VG®, Tri-Ethane 314®,

Tri-Ethane 324®)
Separan (a polyacrylamide) Peroxide precipitation [RF-P262]:
Shell Vitrea oil Plutonium machining [RF-P084, RF-P272, RF-U133]
Sodium 2, 4-dihydroxyazbene Unknown [RF-C211, RF-U182]
Toluene Radiation instrument group after July, 1956
Trioctyl phosphine oxide Building 771 analytical laboratory [RF-C502]
Tributyl phosphate Solvent extraction [RF-P091]
Trichloroethane-perchloroethylene Product R&D [RF-P100] -
mixture (Dowclene EC®,
CSM-320®)
Trichloroethylene (Neu-Tri®, Cleaning concrete, plutonium metallurgical R&D, product

R&D, analytical and mass spectrometry laboratories
[RF-P100, RF-P102, RF-P187, RF-P241, RF-U117]

Product R&D, degreasing, cleaning, density balances
[RF-P100]

Product R&D [RF-P187]

Building 771 analytical laboratory [RF-C502]

Technical staff (1960), spectrograph (1964), site returns
[RF-P085]

Neutron poison [RF-C502]

Thermite reduction [RF-P084, RF-P091, RF-P260]
Direct oxide reduction [RF-P264]

Alloyed with plutonium [RF-C502]

Thermite reduction [RF-P084, RF-P260]

Thermite reduction [RF-P084]

ZPPR [RF-C219, RF-C220]

Production plating, R&D plating [RF-P084]
Plutonium metallurgical R&D [RF-U202]

Plating [RF-P084]

4-46


4.10.3 Radionuclides

A range of activities took place within Building 771, including a wide range of plutonium
processing, recovery, and purification; process development; support; and experimental development
operations. For example, several different TRU elements were handled in the Chemistry R&D Laboratory
areas and Special Recovery areas throughout the history of the building. The RFP also produced
components from other metallic radionuclides (including ”’Np, “Am, **Pu, and “Cm) on a limited
basis for incorporating into pits as “special order” operations. Consequently, any or all of these
radionuclides could be present in the wastes in trace quantities generated during their processing,
including waste generated during recovery operations [RF-P085, RF-P091, RF-P108, RF-P265].
Radionuclides identified in waste from Building 77] are listed in Table 4-25, together with the process
areas in which they may have been used.

Table 4-25, Radionuclides used in Building 771.

Radionuclides
34 Plutonium
“am : DU

EU

4.11 Building 774

When Building 774 was constructed in 1952, its primary purpose was to support Building 771 by
treating its radioactive liquid wastes. Secondarily, it treated radioactively and/or chemically contaminated
liquid waste from the rest of the RFP. The facility was divided into two separate areas or “stages.” The
first stage received and treated only plutonium- and americium-contaminated aqueous liquid wastes. The
second stage received and treated EU- and DU-contaminated aqueous liquid wastes, plus treated
plutonium- and americium-contaminated wastes from the first stage. Aqueous waste solutions that did not
meet the feed specifications for the first or second stage treatment processes were processed separately.
Before the bottle process was developed to treat these wastes in Building 774, the solutions were set up
directly in the waste container or drum and identified as either 741 or 742 sludge. After treatment of these
liquids began in 1967 in the Building 774 bottle process the solutions were processed in an open tank, or.
if in small quanitities, set up directly in the container (bottle) or drum. The solidified liquid waste was
listed as 744 sludge, or special setups. Also in 1966, the Grease Plant began processing backlog and
newly generated organic liquid wastes. This sludge was listed as 743 sludge. Installed in 1966 and in
service in 1967, an evaporator and double-drum dryer began to treat liquids that had accumulated in the
solar evaporation ponds. The dry salt produced was packaged in drums and was listed as 745 sludge
[RF-P047, RF-P085, RF-P098, RF-P260, RF-P264, RF-U115, RF-U1070].

The treatment operations were for the purpose of liquid waste disposal to reduce the volume of
wastes and convert them to a form acceptable for transportation to offsite burial grounds or for release to
offsite surface waters. Treatment operations in Building 774 did not include recovery of plutonium or
other radionuclides. Liquid waste processing involved relatively consistent technology over the years,
with only some refinements to achieve greater treatment capacity and eliminate offsite discharges
[RF-P047, RF-P085, RF-P260, RF-P264, RF-U115).

The Building 774 facility was initially divided into two separate stages, as illustrated in Figure 4-6.

Additional stages and refinements were added over time to reflect the expanded scope described below
[RF-P047, RF-P085, RF-P098, RF-P260, RF-P264, and RF-U115]:

4-49